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23rd IAEA TWG-NPPIC24-26 May 2011, Vienna
Hang Bae Kim (hbkim@kepco-enc .com)
1
Nuclear Safety
Brand Power Leading Role Financing Capability Global Experience
Leading CompanyRegulatory Body
LicensingInspection
Operation andManagement
Design and Engineering Nuclear Fuel Maintenance
and ServicesEquipment Manufacturing
Construction
Ministry of Education, Science & Technology
Research and Development
2
KNSKorea Nuclear
Society
1. Nuclear Industry in Korea1. Nuclear Industry in Korea
Four Units of APR1400 to be Constructed in UAE
Contract Award : Dec. 27, 2009
Completion : Unit #1 by May 1, 2017
Units #2,3,4 : 1 Unit / Year
3
Nuclear Power Plants Export
2. Nuclear Power Plant Status 2. Nuclear Power Plant Status
4
Nuclear Power Plants
Kori 1, 2, 3 , 4Shin-Kori 1, Shin-Kori 2, 3 & 4(Under Construction)Shin-Kori 5&6(Planned)
Wolsong 1, 2, 3 & 4Shin-Wolsong 1 & 2 (Under Construction)
Ulchin 1, 2, 3, 4, 5 & 6Shin-Ulchin 1&2
(Under Construction)
Yonggwang 1, 2, 3, 4, 5 & 6Yonggwang Wolsong
Ulchin
Kori
Seoul
Gyeongju
Radioactive Waste Disposal Facility
(under construction)
In Operation
Under Construction
Planned
21units(18,716 MW)
7units(8,600 MW)
2 units(2,800 MW)
5
21 NPPs supply 35- 40% of electricity
Construction Schedule (5th long term plan)
No. of Units
SWN 1&2SKN 1&2
UCN 5&6YGN 5&6
WSN 2,3&4UCN 3&4
YGN 3&4UCN 1&2
YGN 1&2KORI 3&4
KORI 1
‘72 ‘75 ‘78 ‘81 ‘84 ‘87 ‘90 ‘93 ‘96 ‘99 ‘02 ‘05 ‘08 ’11 ’14 ’18 ‘23
UnderConst-ruction
Opera-tion
SUN 1&2
SKN 3&4
SKN 5&6
PlanPWRPHWR
WSN 1KORI 2
28
20
9
3
TMI Chernobyl
6
Fukushima
SUN 3&4SKN 7&8
3438 NPPs supply 59% of electricity by 2030
7
World Best Operational Performance
1970s
Completion of First APR1400 (’13)
Units complete: 8 unitsFirst Unit complete
1980s 1990s 2000s
Units complete : 5 units
Units under construction:7 units
Units export (UAE) : 4 units
Introduction of Nuclear Power
TechnologyAccumulation
Developmentof OPR1000
Developmentof APR1400
Completion of Kori Unit1 (’78)
Completion of First OPR1000 (’95)
Units complete : 7 units
Nuclear Power Development
※ Source : KHNP
8
9
Nuclear Technology
Power : 1,000 MWeLife Time : 40 yearsConst. : 51 monthsSeismic : 0.2g
Power : 1,400 MWeLife Time : 60 yearsConst. : 54 monthsSeismic : 0.3g
Power : 1,500 MWeLife Time : 60 yearsConst. : 36 monthsSeismic : 0.3g
• Advanced multi-purpose small sizereactor- Electricity generation- Desalination
• Power : 330MWt
OPR1000Optimized Power
Reactor 1000
APR1400Advanced Power
Reactor 1400
APR+Advanced Power
Reactor plus
SMARTSystem-integrated
Modular Advanced ReacTor
3. Design Characteristics of APR1400 MMIS3. Design Characteristics of APR1400 MMIS
10
I&C System Design Features
Microprocessor based digital I&C technology- PLC platform for Safety I&C and DCS platform for Non-Safety I&C
Four (4) channel redundancy for Safety I&C
- Installed in separate channelized I&C equipment room
Multiplexed I/O and redundant communication network - From field areas to I&C equipment rooms and MCR
Diverse Actuation System to cope with the CMF of Safety I&C
Complete electrical, physical and communication isolation− Between redundant safety channels / between safety system and non-safety system
MCR Features
12
I&C System Overview
ProgramServer
GatewayServer
Control & Monitoring Network
QIAS-N(C, D)
Non-safety Components(Sensors, Txs, Pumps, Valves, etc.)
FIDAS NIMSALMSIVMSLPMS
RCPVMS
P-CCSBOP
Controls
NPCSPP&LCSFWCSSBCS
DPS PCSRRS
RPCSDRCS
Remote I/O
ICI Sensors
ENFMSStartup/Control
Safety
FissionChamber
Data LinkServer
Dedicated H/W switchesESFAS
InitiationRT
InitiationMinimumInventory
DMASwitches
DISQIAS-P
PPS/CPCS OM QIAS-N
Operator Console
Safety Console Large Display Panel
Protection System
PPS(4 Ch)
ESF-CCS(4 Ch)
QIAS-P(A, B)
CPCS(4 Ch)
Safety Components (Sensors, Txs, Pumps, Valves, etc.)
Channelized Safety Bus
MTP ITP
CIM
AlarmServer
DBServer
APC-S : Auxiliary Process Cabinet – Safety, CIM : Component Interface Module, CPCS : Core Protection Calculator System, DIS : Diverse Indication System, DMA : Diverse Manual ESF Actuation, DRCS : Digital Rod Control System, ENFMS : Ex-core Neutron Flux Monitoring System, FIDAS : Fixed In-core Detector Amplifier System, ICI : In-Core Instrumentation, NIMS : NSSS Integrity Monitoring System, NPCS : NSSS Process Control System, OM : Operator Module, P-CCS : Process Component Control System, PCS : Power Control System, QIAS-P/N : Qualified Indication & Alarm System - PAMI / Non-safety
APC-S(4 Ch)
DIS
SafetySoft Control
Non-safetySoft Control
Ch. ConfirmSwitches
Control & Monitoring System
APC-S
Common platform for Safety I&C
Common platform for Non-safety I&C
Dedicated equipment for its function
Computer server, monitor & peripherals
Conventional H/W components
Legend
Safety related networkNon-safety networkHardwired Connection
Protection System Overview
DPS (2 CH)
MG set
DRCS
RTSS
PPS (4 CH)
Dedicated Safety Sensors (4 channels)
ESF-CCS (4 CH)
S
ESF Actuation Signals
ESFAS Initiation Signals
Ch A Ch B Ch C Ch D
Ch C Ch D
RT Initiation Signals AFAS
Ch BCh A
Ch N1 Ch N2
RT
ENFMS(4 CH)
CPCS(4 CH) S Non-safety Sensors
(2 channels)
C A
D B
M
MG
G
480 Vac139/240 Vac
AFAS : Auxiliary Feedwater Actuation SignalDRCS : Digital Rod Control SystemENFMS : Excore Flux Monitoring SystemRTSS : Reactor Trip Switchgear System
N2
N1
Soft Control Overview
Non safetySoft Control
PCS NPCS P-CCS
P-CCS FPDs
Control & Monitoring Network
SafetySoft Control
CCG
ESF-CCS
CPM
Soft Control Network
A B C D
Ch. Confirm Switches
ESF-CCS FPDs
PPS
Channelized Safety Bus
Hardwired
CPM : Control Panel MultiplexerCCG : Control Channel Gateway
Serial Data Link
ESF-CCS CIM
Rx Trip on High Containment Pressure
ESF components
Position 4 Display
CPM
ESFASInitiation
RTInitiation
MinimumInventory
DMASwitch
DISQIAS-PPPS/CPCS
OM QIAS-N
Safety Console
Dedicated H/W switches
PPS
DPSAFAS
Isolator
DMA : Diverse Manual ESF Actuation
MG set
RT
APC-S
RTSS
Provisions to cope with CCF
CPM : Control Panel Multiplexer
CIM : Component Interface Module
Protection & Control System Platforms
PLC for Protection System (POSAFE-Q by POSCO-ICT)
DCS for Control System (EXOS by WOORI)
17
4. Major I&C Modernization Projects4. Major I&C Modernization Projects
18
1. Rod Control System (RCS)2. Diverse Protection System (DPS)3. Automatic Seismic Trip System (ASTS)4. Excore Neutron Flux Monitoring System (ENFMS)5. Main Control Room (MCR)
19
- Old system supplied by Westinghouse in 1978 and 1983- New system supplied by KEPCO-E&C and Doosan- Project period : 2008. 3 – 2011. 6
1. Rod Control System (KORI 1&2)
Replacement : Maintain :
RCU : Reactor Control Unit, PAS : Plant Annunciator System PCS : Plant Computer System, BIM : Bank Insertion Monitor
Logic Cabinet Power Cabinets
MG-Set
Power Cables
RCU, PAS, PCS, BIM(*)
Lift Coil Disconnect SW
CRDM
MCB MMI
1. Rod Control System (KORI 1&2)
21
1. Rod Control System (KORI 1&2)Old Cabinets MCB
New Cabinets
22
1. Rod Control System (KORI 1&2)Rod Control Display Cabinet MTP Display
Digital Modules
23
Disconnect cables Remove modules Remove old cabinet
Install channel base Install new cabinet Connect cables
1. Rod Control System (KORI 1&2)
Dismantling and Installation
2. Diverse Protection System (OPR1000)
24
- Objective• To replace PLC-based DPS with FPGA-based DPS
- Project scope• To design and install FPGA-based DPS Cabinet Assembly for
OPR1000 (8 units)
- Project schedule • 2011. 3 – 2015. 3
- Contract participants• Plant Owner : KHNP• System Designer : KEPCO E&C• Supplier : To be determined later
2. Diverse Protection System (OPR1000)
25
- DPS Block Diagram & ReplacementReplacement
PROCESSSENSORS
PZRPRESS
CNTPRESS
SGLVL
TURBINETRIP
ENABLE
MANUALREACTOR
TRIP
TRUBINETRIP
INPUT
120 VacVITAL
POWER
ANALOGINPUT
DISCRETEINPUT
POWERSUPPLY
PROGRAMMABLE
LOGIC
CONTROLLER
OPERATION&
TEST
DPS CABINET
DISCRETEOUTPUT
ANALOGOUTPUT
INITIATIONCIRCUIT
INDICATORSON MCB
MG SET
PLANTCONTROLSYSTEM
PDAS
VALVE&
PUMP
PLANTANNUNCIATOR
SYSTEM
* U5&6 only
2. Diverse Protection System (OPR1000)
26
DPS CABINET
CHANNEL N1
CHANNEL N2
FLAT PANEL DISPLAY
P/S N1 P/S N2
Cabinet Assembly by Supplier
Display Programming by KEPCO E&C
FPGA Programming by KEPCO E&C
3. Automatic Seismic Trip System
27
1. Objective• Trip the reactor at severe seismic event• Enhance the safety of NPP and improve public acceptance
-Project scope• Design and install ASTS for all operating NPPs
• Project schedule • 2009. 9 – 2013. 1
• Hardware• Non-safety grade, Seismic class I• 2 channel 2 out-of 2 energized actuation
3. Automatic Seismic Trip System
28
3. Automatic Seismic Trip System
29
TRIP LOGIC CHANNEL N1
TRIP LOGIC CHANNEL N2
30
4. ENFMS Improvement (UCN 1&2)
- 950 MWe PWR supplied by Framatome in 1983- Project period : 2009.2 – 2012.7
ENFMS(Ex-core Neutron Flux Monitoring System)
To measure reactor power level by monitoring the neutron flux leakage from the reactor vessel
Purpose of improvement project Lower drift and higher reliability by upgrading the old system
Cost savings by means of the reduced inventory of spare parts
The use of single type detector (Fission Chamber)
No replacement of detectors for the lifetime of the plant
B10 for SR and IC for IR are required to replace due to the limited life time
New FC detectors have a 40-year design life
31
4. ENFMS Improvement (UCN 1&2)
32
4. ENFMS Improvement (UCN 1&2)
33
Now To be
The use of signal type of detector SR : B10 FC / IR : CIC FC (SR and IR shares the detector (FC)) PR : UIC FC
The configuration of detector assemblies
4. ENFMS Improvement (UCN 1&2)
5. MCR Upgrade (KORI 1)
34
- Plant • 587 MWe PWR supplied by Westinghouse in 1978• life extension from 30 to 40 years in 2008
- Project scope• replace all MCR equipment • HSIs improvement required by PSR (periodic safety review)
- Project schedule • phased upgrade : 2006. 5 – 2013. 9
- Feasibility study• recommended hybrid type MCR
35
MCR Layout
5. MCR Upgrade (KORI 1)
36
Hybrid MCBNow To be
5. MCR Upgrade (KORI 1)
5. MCR Upgrade (KORI 1)
37
Upgrade Scope
Reduction of numberof Alarm tiles
Compliance toHF guidelines
BISI
New Cable Terminal Board
Recorders IndicatorsSwitch
Standardization M/AStations
Improvementof cable terminals
PlantComputer
Reduction of cables
Needs
Req’t
Review
New :
Advanced:
Present :
Alarm System
VDUs
SafeguardCabinet
ProcessControlCabinet
MCC/SWGR/ETCESFAS
GovernorControlCabinetBISI
Cabinet
MGovernor
Component
OACS
System Integration
PSR Action
ReactorProtection
Cabinet
5. MCR Upgrade (KORI 1)
38
Switch Recorder Indicator
Now
To be
5. MCR Upgrade (KORI 1)
39
Now (Conventional)
To be (Hybrid)
MCR End Point Vision
5. Recommendations5. Recommendations
40
1. Licensing requirements for automatic seismic trip system2. Application of universal (safety+control) soft control3. Harmonization of licensing requirements and process4. Safety critical software development methodology5. Application of new technology (FPGA, wireless …)
End of presentation